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Digital Library / STP / STP484-EB
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Irradiation Effects on Structural Alloys for Nuclear Reactor Applications
Bement AL
Pages: 570
Published: 1970
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Description
Table of Contents
Introduction
Bement AL
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
Discussion
How Do We Solve the Void Problem?
Discussion
Discussion
Discussion
Discussion
Neutron Dosimetry for Reactor Pressure Vessel Applications
Serpan CZ, Morgan WC
Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels
Wullaert RA, Ireland DR, Tetelman AS
The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessel Steels
Brinkman CR, Beeston JM
Evaluation of the Embrittlement of Pressure Vessel Steels Irradiated in JPDR
Kawasaki M, Fujimura T, Suzuki K, Namatame H, Kawasaki M
Demonstration of Improved Radiation Embrittlement Resistance of A533B Steel Through Control of Selected Residual Elements
Hawthorne JR
Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen
Igata N, Hasiguti RR, Yagi E, Nishiike U, Watanabe K
The Effect of Fast Neutron Irradiation on the Mechanical Properties of Some Quenched and Tempered Steels
Hosbons RR, Wotton BL
Structure and Composition Effects on Irradiation Sensitivity of Pressure Vessel Steels
Steele LE
Effects of Irradiation in a Thermal Reactor on the Tensile Properties of Zircaloy 2 and 4 and Borated Stainless Steel
Baroch CJ, Munim AV, Harbinson EN
Influence of Irradiation Temperature on the Tensile Properties of Stainless Steel
Kangilaski M, Spretnak JW, Bauer AA, Wullaert RA
The Effect of Neutron Irradiation on the Mechanical Properties of Zirconium Alloy Fuel Cladding in Uniaxial and Biaxial Tests
Hardy DG
Metallurgical Properties of Cold-Worked Zircaloy 2 Pressure Tubes Irradiated Under CANDU-PHW Power Reactor Conditions
Langford WJ
The Temperature and Neutron Dose Dependence of Irradiation Growth in Zircaloy 2
Harbottle JE
Quantitative Transmission Electron Microscopy of Bubbles in A1 and A1-A1O Alloys
Ruedl E
The Mechanism and Kinetics of Void Growth During Neutron Irradiation
Bullough R, Perrin RC
Void Formation in Proton Irradiated Stainless Steel
Keefer DW, Neely HH, Robinson JC, Pard AG, Kramer D
Considerations of Metal Swelling and Related Phenomena Caused by Fast Neutron Irradiation
Li C-Y, Franklin DG, Harkness SD
Some Observations on the Structure and Tensile Properties of AISI Type 316 Steel as a Function of Fast Reactor Irradiation Temperature
Barton PJ, Higgins PRB
Neutron Dosimetry for Fast Reactor Applications
McElroy WN, Dahl RE
Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components
Moen RA, Tobin JC, Thomas KC
Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures
Beeston JM, Brinkman CR
Effect of Fast Neutron Irradiation on the Creep Rupture Properties of Type 304 Stainless Steel at 600 C
Bloom EE, Stiegler J
Uniaxial and Biaxial Creep Rupture of Type 316 Stainless Steel After Fast Reactor Irradiation
Lovell AJ, Barker RW
Effect of Irradiation on the Mechanical Properties of 19-9DL Alloy
Lowe AL, Baroch CJ
Influence of Neutron Irradiation on the Creep Rupture Properties of a 16Cr-13Ni Steel
Ehrlich K, Böhm H, Wassilew C
The Effects of Helium on the High-Temperature Ductility of Sandvik 12R72HV and Inco IN-744X
Kramer D, Garr KR, Rhodes CG, Pard AG
Correlation Between the Mechanical Properties and Microstructure of Irradiated Iron and Low-Carbon Steel
Stefanovi VM, Milain NLj
Irradiation Effects at Cryogenic Temperature on Tensile Properties of Titanium and Titanium-Base Alloys
Younger CL, Haley FA
Committee: E10
Paper ID: STP484-EB
DOI: 10.1520/STP484-EB
 ASTM International is a member of CrossRef.
0-8031-0014-0
978-0-8031-0014-5
STP484-EB
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